IAEA0925 SHARDA.
SHARDA, Thermal Reactor Isotope Irradiation Analysis
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| SHARDA | IAEA0925/01 | Tested | 11-SEP-1987 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| IAEA0925/01 | NORSK DATA 500 | CDC CYBER 740 |
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3. DESCRIPTION OF PROGRAM OR FUNCTION
SHARDA is a program for assessing Sample Heating rate, activities produced and reactivity load caused while irradiating a small sample in a well thermalised research reactor like CIRUS. It estimates the sample cooling or lead shielding requirements to limit the gamma dose rates due to the irradiated sample within permissible level.
SHARDA is a program for assessing Sample Heating rate, activities produced and reactivity load caused while irradiating a small sample in a well thermalised research reactor like CIRUS. It estimates the sample cooling or lead shielding requirements to limit the gamma dose rates due to the irradiated sample within permissible level.
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4. METHOD OF SOLUTION
Various thermal neutron nuclear data, radiation data of activities produced by neutron capture (of consequence for gamma dose rate estimates) and the isotopic composition of all natural non-fissionable elements are compiled and built into the code. The data for gamma attenuation in lead are also incorporated. Reactivity load per cm2 of a white absorber evaluated at a reference point in a reactor (CIRUS in the present varsion) and the relative thermal neutron flux levels at all permissible irradiation locations in the reactor are also built in. The parameters of interest for a given sample (defined by its chemical formula or mixture specification) and its irradiation specification are evaluated using this inbuilt data library and the analytical expressions for the parameters derived under certain approximations.
Various thermal neutron nuclear data, radiation data of activities produced by neutron capture (of consequence for gamma dose rate estimates) and the isotopic composition of all natural non-fissionable elements are compiled and built into the code. The data for gamma attenuation in lead are also incorporated. Reactivity load per cm2 of a white absorber evaluated at a reference point in a reactor (CIRUS in the present varsion) and the relative thermal neutron flux levels at all permissible irradiation locations in the reactor are also built in. The parameters of interest for a given sample (defined by its chemical formula or mixture specification) and its irradiation specification are evaluated using this inbuilt data library and the analytical expressions for the parameters derived under certain approximations.
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IAEA0925/01
NEA-DB ran the test case included in this package on a CDC CYBER 740 computer in 1.8 seconds of CPU time.[ top ]
7. UNUSUAL FEATURES OF THE PROGRAM
Since the code was basically developed for P.I.R. evaluations in the CIRUS research reactor, the flux levels at various possible irradiation locations and the reactivity worth per cm2 of a white absorber area (at a reference point) built into the code pertain to CIRUS. To use the code for such analysis in any other well thermalised research reactor, these parameters may be appropriately changed. The code can, however, be used as such for most of such analyses, except reactivity load, for any other thermal research reactor by giving the absolute value of irradiating thermal neutron flux as input.
Since the code was basically developed for P.I.R. evaluations in the CIRUS research reactor, the flux levels at various possible irradiation locations and the reactivity worth per cm2 of a white absorber area (at a reference point) built into the code pertain to CIRUS. To use the code for such analysis in any other well thermalised research reactor, these parameters may be appropriately changed. The code can, however, be used as such for most of such analyses, except reactivity load, for any other thermal research reactor by giving the absolute value of irradiating thermal neutron flux as input.
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IAEA0925/01, included references:
- V.K. Shukla and Anil Bajpai:SHARDA - A Program for Sample Heat, Activity, Reactivity
and Dose Analysis.
B.A.R.C.-1259 (1985)
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IAEA0925/01
The test case ran on a CDC CYBER 740 in 43621 (octal) words of main storage.[ top ]
IAEA0925/01
NOS 2.5.1 (CDC CYBER 740) with FTN5.1+650 compiler.[ top ]
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IAEA0925/01
| File name | File description | Records |
|---|---|---|
| IAEA0925_01.001 | information file | 58 |
| IAEA0925_01.002 | SHARDA source program (FORTRAN-77) | 1287 |
| IAEA0925_01.003 | sample problem input data | 5 |
| IAEA0925_01.004 | sample problem printed output | 426 |
| IAEA0925_01.005 | sample problem summary output (TAPE6) | 70 |
Keywords: capture, dose rates, gamma radiation, irradiation, isotopes, radiation heat, radioactivity, radioisotopes, reactivity, shielding, thermal reactors.